Text

Preoperational Environ Radiological Monitoring Program at Fermi-2,Annual Rept 1979.
	ML20005B988
Person / Time
Site:	Fermi
Issue date:	02/29/1980
From:	Daniels R, Englehart R, Smyth R; NUS CORP.
To:	;
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ML20005B986	List: ML20005B985; ML20005B987; ML20005B988; ML20005B989;
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	NUS-3542, NUDOCS 8109160256
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NUS-3542 '

PREOPERATIONAL ENVIRONMENTAL RADI,OLOGICAL MONITORING PROGRAM AT FERMI-2 Annual Report 1979 Prepared for .g O The Detroit Edison Company by Randa!! C. Smyth l

l February 1980 i

Northern Environmental Services Division NUS Corporation 4 Research Place Rockville, Maryland 20850

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Richard W. Englehart, Ph.d. Raphael S. Daniels Project Manager Manager, Manager, Radiological Programs Department Land Resources Unit 8109160256 810914 PDR ADOCK 05000341 R PDR

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, O TABLE OF CONTENTS Section Title Page I. INTRODUCTION 1

A. Site and Station Description B. Objectives and Overview of Fermi-2 Monitoring Program II . PROGRAM DESCRIPTION 4

!!I. SAMPLING METHODS AND PROCEDURES 12 A. Direct Radiation B. Fish C. Shoreline Sediments D. Airborne Particulates E. Water F. Milk IV.

SUMMARY

AND DISCUSSION OF 1979 '* . 15 ANALYTICAL RESULTS O ^-

B.

oirect Radiatioa

. Fish C. Shoreline Sediments D. Airborne Particulates E. Water F. Milk V. REFERENCES

48 APPENDIX A Deviations in the Sampling and 49 Analytical Regime i

APPENDIX B Laboratory Quality Assurance 52 APPENDIX C Analytical Procedures 64 APPENDIX D Reporting of Analytical Results 65 t

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7-j tv LIST OF TABLES Table Number Title Page i Environmental Radiological Monitoring Program 5 1979 2 Sample Locations and Associated Media 8 3 Direct Radiation - Analytical Results 17 4 Fish (Perca flavescens) - Analytical Results 19 Edible Portion Gamma Emitting Nuclides 5 Shoreline Sedimer.ts - Analytical Results 21 Gamma Emitting Nuclides 6 Airborne Particulates - Analytical Results 23 Gross Beta ..

7 Airborne Particulates - Analytical Results 31 Q Gamma Emitting Nuclides 8 Water - Analytical Results 34

, Gamma Emitting tJuclides

, 9 Water - Analytical Results - Tritium 38

, 10 Drinking Water - Analytical Results 39 l Gross Beta 11 Milk - Analytical Results 42 Gamma Emitting Nuclides 12 Milk - Analytical Results - Iodine-131 43 t

l !3 Indicator Location Statistical Evaluation 44 0

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n. %mser Title i

Sampling Locations - By Station Number 10 (Immediate Vicini:1 of Fermi-2) j

Sampling Locations - By Station Number 11 (Greater Than 5 .hiles) :

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NUS COAPORATION

P g I. INTRODUCTION O -

The preoperational radiological environmental monitoring program for Fermi-2 wa initiated on March 15,1978 and will continue until fuel loading, presently scheduled

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for 1981. This program is' being conducted by NUS Corporation under contract wi The Detroit Edison Company (Edison).

This is the second Annual Report for the radiological environmental monitoring program being conducted under the contra This report covers the period December 29, 1978 through January 5,1980 and summarizes the results of measurements and analyses of data obtained from samples collected during this interval.

A. Site and Station Description Fermi-2 is a BWR designed to operate at a power level of about 1150 megaw electrical output with the main condenser circulating water cooled by two natural draft, wet type, hyperbolic cooling towers. The plant is located on approxim 1120 acres about eight miles east-northeast of Monroe, Michigan; thirty miles southwest of downtown Detroit, Michigan; and, twenty-five miles northeast of downtcwn Toledo, Ohio.

Fermi-2, bounded on the east by Lake Erie, is situated in Frenchtown Township in Monroe County, Michigan.

B.

Objectives and Overview of Fermi-2 Monitoring Program United States Nuclear Regulatory Commission (USNRC) regulations requir nuclear power plants be designed, constructed, and operated to keep levels of ;

radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARAX10 CFR 50.34).To assure that these criteria are met, each license authorizing reactor operation includes technical specifications (10 CF 30.36a) governing the release of radioactive effluents, in-plant monitoring is utilized to assure that these predetermined rel ease limits are not exceeded.

However, as a precaution against unexpected and undefined O .

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penes which might allow endue accumulation of radioactivity in any sector of p) i man's environment, a program for monitoring the plant environs is also included.

v De regulations governing the quantities of radioactivity in reactor effluents allow rwclear power plants to contribute, at most, only a few percent increase above normal background radioactivity. Background levels at any one location are not constant but vary with time as they are influenced by external events such as cosmic ray bombardment, weapons test fallout, and seasonal variations. These levels also can vary spatially within relatively short distances reflecting variation in geological composition. Because of these spatial and temporal variations, the radiological surveys of the plant environs are divided into preoperational and operational phases. The preoperational phase of the program of sampling and measuring radioactivity in various media permits a general characterization of the radiation levels and concentrations prevailing prior to plant operation along with an indication of the degree of natural variation to be expected. The operational phase of the program obtains data which, when considered along with the data obtained in the preoperational phase, assist in the evaluation of the, radiological impact of plant operation.

OV implementation of the preoperational monitoring program fulfills the following objectives:

1.

Evaluation of procedures, equipment and techniques 2.

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1 Identification of potentially important pathways to be monitored l af ter the plant is in operation 1 .

3.

l Measurement of background levels and their variations along l1 potentially important pathways in the area surrounding the plant.

4. Provision of baseline data for statistical comparison with future l

operational analytical results, i

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7 ,. Sampling locations were selected on the basis of local esulogy, meteorology, U physical characteristics of the region, and demographic and land use features of the site vicinity. The preoperational program was designed on the basis of the USNRC Branch Technical Position on radiological environmental monitoring as issued by the Radiological Assessrnent Branch (March, 1978).(1) . Edison is presently evaluating the parameters associated with expanding the monitoring program to inciude new guidelines in the USNRC Branch Technical Position on Regulatory Guide 4.8 (November 1979, R(vision 1) 2) and pertinent aspects of USNRC Regulatory Guide 1.97, proposed Revision 2 (December 1979).

In 1979, the radiological monitoring program included the measurement of ambient gamma radiation by thermoluminescent dosimetry; the determination of gamma emitters in shoreline sediments and fish (Perca flavescens); the determination of gross beta and ga'mma emitters in air particulates; the measurement of gross beta in drinking water; the determination of gamma emitters and tritium in drinking water and surface water; and the determination of gamma emitters in milk at the

A control location.

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. s 11. PROGRAM DESCRIPTION Fif teen (!$) locations within a radius of about 15 miles from the Fermi-2 site were monitored. The number and location of monitoring points were determined by

, considering the locations where the highest offsite envir'onmental concentrations

! have been predicted from plant effluent scarce terms, site hydrology, ar.d site i

meteorological conditions. Other factors considered were population distribution, ease of access to sampling stations, security and future program integrity.

The preoperational environmental radiological monitoring program for Fermi-2 is

, summarizea in Table 1. Sample collection at Station 15 (drinking water-control) and the indicator milk locations are expected to be implemented in 1980. Gaseous radiciodine monitoring is also scheduled to begin in late 1981 This implementation will be correlated \vith the finalization of the fuel load date for Fermi-2. Table 2 describes sample locations, associated media, and approximate distance and direction from the site. Figures I and 2 designate sampling locations by station

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I t..vironm;;ntal Rtdiological toring Program, 1979 Analysis Sample Media Station Number and Location Sampling Frequency Type Frequency Direct Radiation i Telephone pole #DE693511-6 Continuous sampling Gamma dose Quarterly 2 Tree at the termination of TLDs changed Brancho Street quarterly (2 TLDs/

3 , Tree adjacent te Swan Boat station Club 4 Site Boundar/ and Toll Road, Telephone Pole #DE 762 356 C 5 Site Boundary and Toll Road, Telephone Pole #DE 56R 776 35 G5 6 Site Boundary and Toll Road, .

Telephone Pole 7 Doty Farm, N. Custer Rd.

(Control)

I' Fish 16 Fermi-2 discharge Semi-annually Gamma isotopic Serra-annually y, '

Yellow Perch (edible portion)

(Perca flavescens) 11 Control in vicinity of Celeron Island Shoreline 3 Pt. Aux Peaux, 110' offshore Sedirnents(2) sighting directly to land-based water tower .

9 Fermi-2 discharge Semi-annually Gamma isotopic Semi-annually 10 Estral Beach, 300' offshore sighting directly to land-based windmill i I

Samples analyzed in duplicate / replicate.

Lake Erie cun~ent patterns in the ren i!-2 area fluctuate in opposite directions along slioreline ,

contours for approximately equal durstions during an annual period. As a result, no " control" I is established, j l

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Environmental Radiological Monitoring Program, 1979 Sample Medid Analysis Station Number and 1.ocation Sample Frequency Type Frequency Fish Direct Radiation Same as first year

, Shoreline Sediments Same as first year Same as first year Airborne i Particulates Telephone Pole #DE6935 H-6 4 Continuous sampling, Gross beta Site Boundary and Toll Road, change filters weekly Weekly -

Telephone Pole #DE 762 356 C follot ing each 5

Site 1%undary and Toll Road, filter change Telephone Pole #DE 56R 776 35 G5 7

Doty Farm, N. Custer Rd. (Control) Gamma Isotopic Quarterly-Composi by location m

Surface Water 12 Unit i Raw Lake Water Monthly Intake Structure Gamma isotopic Monthly '

14 Trenton Power Plant intake Structure (Screenhouse #2)

Tritium . Quarterly 4 g)

(Control) composite by location Drinking Water 13 Monroe Water Station Monthly Gross beta (2) Monthlyg) 1 (g)

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Environmental Radiological Monitoring Program,l' 7'J)

Sample Media Analysis Station Number and Location Sampling Frequency Type Milk Frequency Indicator locations 1. Monthly Camma isotopic

2. Semi-monthly 1. Monthly Iodine- 131 2.

when animals on Semi-mont) pasture when anima j 7 on pasture Doty Farm (Control) l (1)

(2) Simples analyzed in duplicate / replicate.

If gross beta in air or water is greater than 10 times the mean of control samples for any medium, gamma isotopic analysis performed on individual samples.

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To be finalized af ter milch animal census is conducted.

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Sample Locations and Associated Media Station Distance from Number (I Direction Reactor (Approx.) Description Media

! NE 1.3 mi. Telphone Pole #DE6935 H-6 Direct Radiation Radioiodine Particulates 2 NNE 1.1 mi. Tree at the termination of Direct Radiation Brancho Steet (private res' fence)

'3 N 1.1 mi. Tree adjacent to Swan Boat Club D! rect Radiation 4 NNW 0.6 mi. Site Boundary and Toll Road, Direct Radiation Telephone Pole #DE 762 356 C Radioiodine Particulates m 5 NW 0.6 mi. Site Boundary and Toll Road, Direct Radiation Telephone Pole #DE 56R 776 35 G5 Radioiodine Particulates 6 WNW

0.6 mi. Site Boundary and Toll Road, Direct Radiation Telephone Pole 7 W 15 mi. Doty Farm, N. Custer Road Di' rect Radiatiori (Control) Radioiodine Particulates Milk 8 5 0.9 mi. Pt. Aux Peaux, 110 f t. offshore Sediment sighting directly to land based water tower 9 E 0.2 mi. Fermi-2 discharge Sediment 10 NE I .1 mi. Estral Beach, 300' of fshore Sediment sighting directly to land based windmill l -

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1 Alst.t. 7 (t i.e.t e .9 Preoperational Environmental Radiological Monitoring I'rogram, l'etim-2 Sample Locations and Associated Media Station Distance from Number _(I Direction Reactor (Approx.) Description Media 11 NNE 9.5 mi. Control in vicinity of Perca flavescens Celeron Island 12 SSE 0.4 mi. Unit i Raw Lake Water Surface Water intake Structure 13 S 1.2 mi. Monroc Water Station Drinking Water 14 NE 13 mi. Trenton Power Plant intake Surface Water Structure (Screenhouse //2) 15 NNE

20 mi. Detroit Water Station 2) Drinking water (Fighting Island) 16 E 0.4 mi. Fermi-2 discharge Perca flavescens (1200 f t. offshore)

III indicator milk sampling locations will be finalized af ter milch I animal census is conducted.

(2) Access to this location not finalized.

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Ill. SAMPLING METHODS AND PROCEDURES To derive meaningful and useful data from the environmental radiological monitoring program, sampling methods and procedures ,are required which will provide samples represeritative of potential pathways of the area. During the preoperational phase of the program, samples are collected and analyzed not only to obtain background radiological levels, but at the same time to acquire experience with the sampling methodology and procedural format dictated by site specific requirements. (4)

A. Direct Radiation Thermoluminescent dosimeters (TLDs) were used t determine the direct (ambient) radiation Ic.els at seven (7) monitoring points. The locations were selected by ranking the mixed-mode X/Q values. Stations I through 6 are situated in the six calculated highest sectors around the plant site. Station 7,* the control, is located approximately 15 miles west of Fermi-2 in the least prevalent wind direction. The O selec11ee ef the TtD recetiees feiiows the suieeiines ee1,imee in the uSNRC ereech Technical Position on Radiological Environmental Monitoring (March,1973).

Duplicate dosimeters of CaSO4 : Dy in teflon, were deployed at each location and exchanged on a quarterly basis by an NUS environmental scientist.

To minimize the in-transit dose contribution, the dosimeters were annealed close to 1

the site within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to f. eld olacement. Freshly annealed control I

dosimeters were sent along with the exposed field dosimeters to determine the exposure received by the dosimeters in transit from the site to readout in j Rockville, Maryland. Calibrations of the dosimeters were performed by obtaining accurately known Cs-137 radiation exposures.

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. B. Fish

, Because of its importance to both commercial and recreational fishermen, and the predominance of th- species in local waters, yellow perch (Perca flavescens) were Q

p 12 NUS CORPO AATION

collected for the monitoring program. As described in Table 1, perch were (o

V) ce!!ected from Lake Erie in the vicinity of the Fermi-2 discharge (Station 16). The control locatior, in the vicinity of Celeron Island (Station !!) approximately nine (9) miles NNE of the plant yielded only the fall sample as discussed in Appendix A.

Using a passive collection technique, an experimental giff net (mesh ranging from approximately 0.5 to 3.5 inches to decrease size selectivity) was set at each sampling location by biologists from The Detroit Edison Company. The net was retrieved af ter approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Entrapped, surviving species other than yellow perch were released.

C. Shoreline Sediments Sediments were collected from three (3) locations by biologists from The Detroit Edison Company. Samples were taken with a Ponar dredge from the vicinities of Point Aux Peaux (Station 8), Fermi-2 discharge (Station 9), and Estral Beach (Station 10). The locations are shown in Figure 1.

g D. Airborne Particulates O

Airborne particulate sampling was initiated on December 30, 1973 af ter approx-imately two months of trial operation. Sampling was performed by a RADeCO continuous low volume air sampler (Model HD-238) by which particulates were collected by drawing air through a 47-millimeter diameter glass fiber filter. The sampling systems are housed in ventilated wooden cabinets bolted to telephone poles.

The air particulate sampling network consists of four (4) stations; one is located at Estral Beach, two are located at the site boundary along Toll Road; a control station is situated at the Doty Farm, approximately 15 miles west of Fermi-2.

These locations are identified in Figures 1 and 2 and described in Table 3.

The samplers were run continuously and the filters exchanged weekly. The elapsed time of sampling was recorded on an elapsed time meter. Total air volume was y

13 NUS CO APO AATION f

i

calculated from the initial and final flow rates recorded by the Site Technician.

O calibrations of each air sampler were performed on December 30,1973, April 1, 9

1979, July 8,1979, September 29, 1979, January 5,1980, and following major repairs.

. E. Water -

i The water sampling network consists of three (3) stations, two (2) surf ace and (1) drinking, as identified in Figures I and 2 and described in Table 2. A Horizon Interval Sampler was used to collect a small volume of water per day. This was automatically composited into a five (5) gallon container. The sample was collected monthly by the Site Technician. The collection of drinking water was i scheduled to begin January 1979 at Station 15 (Detroit Water Station, Allen Park, Michigan). The appropriate instrumentation will be installed and sampling initiated by the Site Technician immediately upon notification by Edison that access to Station 15 has been granted by the City of Detroit.

i

F. Milk p

O

- Milk samples were co!!ected monthly from the Doty Farm (Station 7) on North Custer Road. As a preservative, formalin was added to each sample at the time of f

collection.

E

On April 22, 1979 and May 13, 1979, milk was collected for I-131 analysis. Iodine t

,' carrier and formalin were added to the samples at the time of collection. Sampling i and analysis for this isotope was ended af ter the May sample as a result of the j revised fuel load date for Fermi-2. .

i r

I o -

V.

14 NUS COAPORATION

I i

i iA IV.

SUMMARY

AND DISCUSSION OF 1979 ANALYTICAL RESULTS

!. V Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below. The procedures and specifications followed in the laboratory.for these analyses are as requited in Section 5.0 of the Environmental Systems Group Quality Assurance Manual, issue B, of NUS I Corporation and are detailed in the NUS Radiological Laboratory Manual -

" Environmental Monitoring and Radiological Services Procedures /Terk i instructions."

! Radiological analyses of environmental media characteri.tically approach and frequently fall below the detection limits of state-of-the-art measurement methods.(4) The use of "LT" in the data tables is the equivalent of the less than symbol (<) and is consistent with the NUS Radiological Laboratory practice of data reporting. The number following the "LT"is a result of the lower limit of detection l

. (LLD) calculation as defined in Appendix D. NUS analytical methods meet the LLD requirements addressed in Table 2 of the USNRC Branch Technical Position (November 1979, Revision 1).(2)

Tables 3 through 12 give the radioanalytical results for individual samples. A statistical summary of the results appears in Table 13. The reported averages are based only on concentrations above the limit of detection. In Table 13, the fraction (f) of the t-tal number of analyses which were detectable fo!!ows in parentheses.

Also giver parentheses are the minimum and maximum values of detectable activity ct.: . .g the report period.

O 15 NUS CORPORATION

i I

'O A. Direct aeeietion f Environmental radiation dose rates determined by thermoluminescent dosimeters i (TLDs) are given in Table 3. Duplicate TLD badges of four read-out areas each were deployed at each loc'ation quarterly. The mean values of four readings (cor-rected individually for response to a known dose and for in-transit exposure) are

. reported as "a" and "b".

1 A statistical summary of the data is included in Table 13. Individual measurements of external radiation levels in the environs of the Fermi-2 site ranged from 0.11 to 0.19 mR/ day. Annual levels ranged from 47 to 62 mR/ year. Oakley calculates

an ionizing radiation dose equivalent of 88.8 mR/ year for Michigan, including a terrestrial component of 45.6 mR/ year and an ionizing cosmic ray component of

43.2 mR/ year. Since Oakley's values represent averages covering wide

j geographical areas, the measured ambient radiation average of 56 mR/ year for the immediate locale of Fermi-2 may not be inconsistent with Cakley's observations.

, Significant variations occur between geographical areas as a result of geologic

O composition ene eititede eifferences. Ternperei verie1 ions reseit fro m chenses in

[ cosmic ray intensity, local human activities and factors such as ground cover and l : Oil moisture.

I i

i 5

O 16 NUS CCAPORATION

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, l B. Fish

.O:

l$ The results of gamma analyses performed on yellow perch (Perca flavescens) col- !

I lected during 1979 are presented in Table 4 A statistical evaluation is given in i

j Table 13. Naturally occurring K-4G constituted the major detectable nuclide

activity in the flesh portion of the fish. The Cs-137 concentrations are attributable l to global fallout. The other isotopes identified in the samples are part of the decay chains of naturally occurring uranium and thorium.

t t

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18-NUS COAPORATION j L

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19

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v' k

! C. Shoreline Sedjments The processes by which radionuclides and stable elements are concentrated in l

bottom sediments are complex, involving physicochemical interaction in the en-a vironment between the various organic and inorganic mate' rials from the watershed.

j These interactions can proceed by a myriad of steps in which the elements are adsorbed c:. or displaced from the surfaces of colloidal particles enriched with j chelating organic materials. Biological action of bacteria and other benthic j organisms also contribute to the concentration of certain elements and in the acceleration of the sedimentation process.

t Results of the gamma isotopic analysis of the sediments sampled from the Fermi-2 i

)

environment are given in Table 5. The average, fraction of detectables, and range of radionuclide concentrations are summarized in Table 13. Naturally occurring K-l

' 40 was the predominant radionuclide detected in the samples.

t Cs-137 was identified in the sample collected from Station 9'in June and October.

}

Due to its presence in global fallout as well as the nonhumogeneity typical of lV sediment samples, the occasional detection of this isotope is not unusual.

i i

O s !

20 NUS CORPOAATION

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9 D. Airborne Particulates O

The weekly gross beta results for airborne particulates are listed in Table 6. The .

results of gamma analyses performed on quarterly composited filters, by location, are given in Table 7. A statistical summary of the data is provided in Table 13.

In considering tabulated results which include gross activity measurements, it is important to keep in mind the inherent limitations of gross beta counting for mixtures of unknown activities. The counting efficiency of an unknown mixture of activities varies considerably with the particle energy and the amount of absorbing material in the sample. Because of this, the results of gross activity measurements are difficult, if not impossible, to interpret.

As indicated in Table 7, the majority of gamma emitting nuclides identified in the quarterly composite samples were of natural origin. The detection of Ce-144 in the Station 5 composite for Q2 and the occasional identification of Cs-137 are likely to be attributable to global f allout.

O.

\

(_)

y 22 NUS CORPORATION l

~ '

~~ =e

. n_ __ _ _ _ ,

(es e.. e .

t%,. I.sev6oese..cnt.sl it.nete..

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(,4 M. .s t.ee ...g 84..y,. .esen , I'.ee e-2 l'rtw r.ateosul, l*#71 Air I;4s t u ut.ites Arulytaral itesselts - Gross ik ta itewits ni swists of 10'Ilirs/m' . 2.s ,

i Station FJuantier I Montti Mmpling lyriod Average I 4 3 7 Jaswear y 12/10/18 a 42 _ 4 60 ) 39 -

4 t l ,. 4 i to b 19 6 - 49 _. 7 38 6-

)) . 6 1/6/19 mean 40 . ) 14 6 )& . ) 38 . ) 42 13 1/6/19 a 44 .7 16 9 )) .7 67 8 to b 4) .7 70 1 48 7 65 8 i 1/12/7* mean 44 -./ 73 6 -

30 7- 66 _. 8 18 _. 21 l N , 1/12/19 a 10 6-63 7 78 7 69 _. )

g j to b 3) .6 77 7 83 7 70 . 7 t/20/19 mean 32 6 71 7 80 7 70 . ) 68 2) 4 1/20/19 a ,

2) .) 1) .7 63 7 44 .6 to b 22 . ) .

60 7 . 6) -.7 47 _. 7 1/21/19 measi 22 . > 16 e 7 6) 7 46 6 13 17 * ,

l .'

I Febrisary 1/21/19 a 24 . 3 II .6 31 .) 19 . )

i tu b 26 . ) 26 e 6 )) .6 28 6 i 2/3/19 esecan 2) .. ) 28 .

6 I? 6 24 6 21 7 2/3/19 a 19 .

8 110 e 10 100 9 90 .

Y to b 68 .8 86 9 8) . 8 10 8 l 2/9/19 rev.an 10 8 98 . 10 92 8 80 8 8) . 25 2/9/19 4 40 . ) 16 . f. 31 6 31 .6 to b 44 .6 39 . f. 60 . f. )? . 6 2/11/19 sier.ari 42 6 is . 6 %.6 31 6 )2 ? 14 4

e

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I 4 3 7 Fetit uary 2/17/19 a 43 6 36 7 63 7 38 7 ,

(cont.) to h 46 6 16 7 6) . 7 58 7 2/24/79 mean 44 . 6 36 7 64 . 7 38 7 36 17 Marrli 2/24/19 a 41 ., 6 61 7 64 .6 )7 1 to b ,

40 . ) 61 7 6) . 6 38 6 1/4/19 mean 40 6 62 7 64 6 38 6 34 22 to A

3/4/19 a 30 6 44 .7 43 6 31 7 to b 12 6 48 .7 39 6 14 .7 3/10/77 inean il . 6 42 7 41 6 36 1 38 , 10 1/10/19 a 40 6 6) . 8 64 .7 31 7 to b 49 A 62 e 7 67 7 M.7

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3/l?/19 siecan 44 . 6 44 ., 8 66 7 58 7 58 e 20 1/87/19 a 31 . 6 45 7 ?) .) h.7 to b 34 . 6 41 . 7 2) .) 48 .1 3/21/19 sewan 12 . 6 4* .1 2) . ) 18 1 34 18 3/23/19 a n > 2a . > 46 .> 47 6 to is %.. ) )) > )) -.6 30 .

6 4/1/19 ene n 3) . ) 10 . ) 30 6 48 6 41 . 20

y--

ew..,...e., e er .

Aer t*.a. IH eel aies As.aly t et .el fictult h - Csons Skta licsults in inists of 10gWi/m' . Zo Moeitti keenpimg Period Station Nunileur Average ' '

I 4 5 7 April 4/1/19 a 30 6 50 7 34 5 33 4 to b 11 . 6 46 7 39 6 34 3 4 4/8//9 measi 32 3 6 48 7 36 6 34 .4 38 14 4/8/19 a 10 . ) 4) .8 23 . ) 29 4 to b is . 6 30 8 26 . ) 30 e 4 4/l4/19 mean le . 6 48 8 24 . > 30 . 4 79 ., 29 kJ 4/14/19 a 41 .5 56 e 1 22 ) )) .9 to b 34 .5 5) e 6 28 3 32 9 4/22/19 mean 38 5 36 . 6 25.> 32 9 38 27

~

4/22/19 a ll) . 48 28 6 46 6 22 10 to b 62 5 20 . ) 42 6 22 . 11 .

4/29/19 seican 85 e 26 2't . 6 44 .6 22 10 44 . 61 May 4/29/19 a 21 5 31 . 7 84 31 .I to b 28 . ) 44 .6 84 17 7 3/6//9 neean 25 . 1 48 6 34 34 .7 30 33 3/6/19 o 40 3 (so . 6 22 4 4) . 10

io h n.5 si , 6 22 4 41 .9 i 3/11/19 meaes 35 5 38 6 Il . 4 43 . 10 )) . 18

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Analysn I licsults . Causs sk ta liessiles in units of 10gCi/en' . 2a Monus Sampling IVsiod :;tatson fiumber Average 1 4 1 7 May (cont.) 3/13/19 a 22 3 68 8 29 . S 63 . Il to b 21 5 68 8 28 3 ts 6 . 10

$/19/19 enean 24 .> 68 8 28 . ) 14 . 10 44 . 42 3/19/19 a 37 5 53 6 24 . 3 38 7 to b 33 . S Si .6 22 5 Il e 7 3/21/19 inean 35 _. 5 St._. 6 23 _. 5 38 _. 7 38 _. 26 g

CD an= 5/21/19 a 37 . > >>.7 14 . 2 NS to b 30 . > 32 7 il . 2 6/3/19 . mean 34 . 5 12 7 14 e 2 31 38 6/3/19 a 31 6 66 1 38 4 NS ,

to b 44 6 68 7 17 ., 4 6/10/19 mean 48 6 67 . / 38 4 31 . 29 6/10/19 a 49 .6 64 .1 12 . ) 33 6 to b is 7 . 69 . 8 )0 6 34 . 6 6/17/19 encan 48 6 66 8 il . 6 34 . 6 >0 26 6/11/19 a 32 . ) )h .6 28 4 26 . )

su b 17 . ) 41 6 10 4 26 . )

6/24/19 mean n.> 40 . 6 29 . 4(4) 16 . ) 35 . 14 si, 23/19 a 18 . 6 14 .8 12 . I 18 . )

tu la 4) .6 18 .8 14 . ) 12 . >

//l/19 ene.an 40 6 /6 . 8 11 . 3 10 e 1 40 . 31 a

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....,on... ental n aa.....g.. at uon u.r.ng is ograin . : cen.. 2

[V3 li e ig>cr a i n>nal, 1979 Air l'ar t scula t es ,

Analytical licsults - Gross lieta Itesnits in i nits of 80pCifn.' . 2a Montti 5anipling lYriod Station Nuniitier Average II I 4 3 7 July 7/1/19 a 14 3 4 68 8 N5 28 3 ,

to b 11 7 70 7 29 . )

7/8/19 mean 16 6 69 8 28 . ) 38 36 7/8/79 a 26 . 4 30,. 4 N5 32 3 to b 31 4 33 . ) 39 . )

7/l)/19 mears 28 4 32 4 36 . > 32 8 N .

N 7/15/19 a 34 6 29 6 N5 13 3 to b 27 6 32 6 13 . )

1/22/19 ancan 30 6 30 6 14 .3 2) . 18 7/22/19 a 10 3 24 .3 32 + 3 NS to b 7. 3 24 .3 31 e 3 8/5/19 n.can 83 . 2 4" . 3 32 3 21 + 24 August 8/)/19 a NS N% 20 3 NS to la 11 . >

8/!?/19 nican 18 . ) 18 3 8/12/19 a NS NS 11 .6 13 . S to le 2) . f. 12 . )

8/19/19 encan 28 .6 12 . ) 20 2) 8/ tv// J .s NS N% 41 .6 2% .6 to ts 36 e 6 18 . )

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14csults in isnits of 80' g4's/ n . 2e l

Montle Sainpling Period Station Nuniber Average (II 1 4 5 1 October 10/1/19 a N5 N5 N5 91 j (cont.) to b 12 5 .

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to b 31 .5 ,

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12/8/79 mean 10 . ) 30 5 12/8/19 a 18 3 28 3 5 17 3 NS I to b ?0 3 24 .S 19 )

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22 1

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Gamma emitting nuclides and tritium for all water samples are reported in Tables 3 and 9, respectively. The gross beta results for the drinking water samples are presented in Table 10. Table 13 gives a statistical summary of the water analytical results.

l The only detectable gamma activity during the reporting period was naturally occurring Ra. 226 and K-40.

Detectable tritium concentrations ranged from 190 to $20 pCi/l for all monitoring stations. These measurements are not inconsistent with typical environmental levels identified at other f acilities.

The gross beta activity for drinking water at Station 13 was consister.t daing the reporting period with an overall mean of 2.1 pCi/1. This number was calculated from detectable mee urements only.

i 1 ,

33 l

l NUS CORPORATION

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i i Asts t. es (roe i Enviroewisent.nl Itatfeulogu .nl Monitoreng Prograin, l'er ens- 2 l's coper .s tional, 1979 l WJter

Analytical itesults - C.asnena Emitting Nm lules i

Cornposasong hmpling p&/l Do_

Montti l oca tion Mn- 54 Fe-19 Co 18 Cu-60 Zn- 6 5 Zr-Nb-9 5 Cs-Il4 Cs-137 na-La-140 K-40 Ita-226 Other s Agvil 12 a LT 10 LT 16 LT l) I. T 9 L T 17 LT 7 LT l) Li IS LT ll NI) Nie ND b LT 14 LT 16 LT l) LT 9 L T 21 LT 5 L T 14 LT 8 Li ll ND ND ND encan LT12 LTf6 LT l} LT 9 L1 ?! LT 8 L T 14 LT12 L T 11 l 14 No data f

j ll a LT 4 L T 10 iT 3 LT 4 LT 7 LT S LT 3 LT 7 L T 10 ND NO NI) b LT 4 LT ll LT 5 LT 4 LT 9 1. T 3 LT 4 LT 1 L T 11 ND ND ND encan LT 4 LT 11 LT 5 LT 4 LT 5 LT 3 LT 4 LT 6 L T to May 12 a LT I4 LT 20 1.T 14 LT 9 LT 16 LT 7 LT12 LT 8 1.T 8 ND ND ND 1

b LT I) LT 20 LT I) LT 9 L T 19 LT 8 LT l} LT S LT 8 NI) ND NO nican L T 14 LT 20 LT14 LT 9 LT18 L i' 8 LT12 LT 8 LT 8 I4 No data

'I a LT10 LT 28 LT 9 LT 9 L T 21 LT 8 LT IS LT IS LT 13 NI) NI) ND i 63 b LT 1 LT 22 LT 9 LT 9 L T 18 LT 9 LT10 LT 9 LT 8 ND ND

" encan LT 8 LT 22 L' 9 LT 9 LT 20 LT 5 LT 12 LT12 LT12 i

Dane 12 a LT 9 LT 20 LT le LT 9 L T 18 LT 7 LT12 LT l) LT IS NO ND ND I b LT S L T 19 LT 10 LT 9 L T 20 LT 8 LT 9 L T 10 LT IS ND ND ND ane.sn LT 8 L T 20 LT 12 LT 9 LT19 LT 8 LT 10 LT 12 LT 1) 14 No d.sta

1) a LT 84 LT18 t T !4 LT 9 LT 20 LT 7 LT 9 LT 7 LT IS ND ND ND b LT 4 LT 1) LT 5 LT 3 Lt 8 LT 6 ? LT 4 LT 3 LT 3) ND ND ND j encan LT 9 L1 16 i T 10 LT 6 f.T I4 LT 6 1. T 6 LT 6 i T 2) i i

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i Waaer

Analytical liesults - Gamma Lenittmg Niu ledes g4's/l I 2. K-40 Ra-226 Ott.crs Zn-61 Zr.Nt.-91 C s- 114 Cs-817 lu-La.140 Compositing Sampling Mn 54 Fe-19 Co18 Co 60 ND Montti Location 120! 90 ND LI 20 l.T 16 LT82 L T 17 LT 18 ND ND ND LT 12 LT19 LT l) LT L1 1 LT 9 LT 6 LT 6 LT 6 Octuber 12 a LT 8 LT 6 4 LT 9 L T 12 LT82 (1/2) b L14 L T 14 LTll t. T 9 nican LT 5 LT 14 LT10 1. T 6 14 No data LT 1 NO ND ND LT $ t.T 6 LT 9 LT 6 LT 4 LT 9 LT 6 f.T 6 LT 26 110!)0 90 I40 ND l

LT S LT 7 iT4 13 a LT 4 LT12 LT 6 LT 4 LT 8

t. T 4 1. T 6 LT 16 (1/2) (1/2) b LT 4 LT 8 f. T 6 incan LT 4 LT10 LT 6 ND Nil ND LT 7 LT16 LT 11 LT la LT I) LT 18 130I)0 90I40 ND 12 a LT 10 LT IS LT 8 LT 1 LT 8 LT 4 LT 4 LT 4 LT 7 (t/2) (1/2)

November LT S LT 7 LT 6 LT 8 LT 8 LT 9 b

LT 11 LT 7 LT 5 L T 12 LT 8 mean LT S ND 100I60 ND L T 11 LT14 LT 17 I T 18 LT12 91I)) ND ND a LT 11 :.T 20 LT 8) LT 9 L t 12 LI 6 LT 6 LT 6 LT 6 97I46 It b LT 4 LT10 LT 4 LT 4 LT 64 LT 10 LT12 L T 12 LT 9 mean LT 3 LT IS LT to LT 6 120!60 ND ND tT 17 LT 15 LT IS LT IS L T 12 150I 60 ND ND 13 a LT l) LT 18 LT 11 LT 9 t.T 20 L T 16 LT IS LT16 LT l) 140I 60 b LT12 LT 17 LT 1) LT 9 I.T 16 LT l) L T 16 LT 12 d socan L T 12 L T 18 LT 82 LT 9 LT is IlC I60 NO ND

8. T 9 1.T 22 L T' 16 LT 11 L T 11 1 T 11 140I 80 ND 'ND 12 a L T 12 L T 21 LT I) l i 19 L T 15 L T ll i T 19 L T is 110! /0 December b L) 12 LT 21 LT l) 4. T 8 L T 20 LI 16 LI 12 LT18 LT 18 means t.T 12 LT 21 LI 14 Li 8 180I l0 ND ND 11 17 f.T 13 L T 12 LT l) LT18 140!70 ND NI) 14 4 LT10 LT 20 LT 11 t.T iT99 1. T 20 t T 11 L T 16 L T 14 t T 21 1/0!70 b LT IS LT 24 LT l} I.I 18 8 f ,8 6 LT 14 LI 14 LT 20 incan L T 12 LT 22 LT 12 LT 9 ND ND NI)

L I 24 LI 18 f.T 12 L T 14 LT 84 te,0!a0 ND ND a L T 18 1.T IS L T 12 lT1 1.T 21 1.T l) LT 17 t t 15 t1 18 l)

L T 11 LT 211.T LT84 It IIII 89 LI 14 LT 84 ti 16 (1/2) b LT ll L T 21 LT 22 1 T l) mean (I) Surf ace Water (2) Drinking water (3) Simple average (rounded) I sempic average (ruiputed)

(4) Insollnient sample for analysis (3) 1.T Lew Tlian (6) ND a Not Detecteil (1) fraction in puentheses mdecates errmber of detettat,les over numt>cr of analyses (8) V.nJ.ilism (Lenpler tue ned oil dining e offet Hon persod)

. - g ,

p

2- t i

TABLE 9 Environmental Radiological Monitoring Program. Fermi.2 Preoperational. 1979 t Water Analtyical Results Tratsum Quarterly Compes4te. By Location Sam %ne Location , pCi/t I 7e Qua.ter 1 12

' a 220 170 b gy) 190i170 mean 200 : 170 l' U I a LT 300 b 390 180 '5' mean (T/2) 13

' a 190 170 b 270 ! 170 mean 230i170 2 12 a LT 300 b LT 300 mean LT 300 14 a LT 300 b LT 300 mean '.T 300 13 a LT 300 b LT 300 mean LT 300 3 12 a 270 : ISO b 220 . ISO mean 240{ ISO 16 a 330 180 6 320 ! 190 mean 4205&&-

13 a 330 180 b 220 7 180 mean 230iISO I 4 12 e LT 300 b LT 300 rnean LT 300 la a .

LT 300 b LT 300 mean LT 300

(

13 a LT 300

( b LT 300 l mean LT 300 (1) Surf ace water (2) Drinking water

' (3) Simple average (roundec) . simp:e average (rounded)

, (4) LT = Less than (3) Fraction in parentheses andscates no. of detectables/no. of analyses i

I O -

38 w

TABLE 10 0

Environmental Radiological Monitoring Program, Fermi-2 Preoperational, 1979 Drinking Water - Analytical Results - Gross Beta Compositing Month Sampling Location pCi/l*2a January 13 a 2.8 2 0.8 b 2.1 0.7 mean( g ) 2.4 + 0.S February 13 a 2.8 + 0.6 b 3.6 + 0.7 mean 3.220.6 March 13 a 2.4 + 0.6 b 2.0 ! 0.7 mean 2.2[0.6 April 13 a

2.1 0.6 2.5 + 0.7 b

mean 2.330.6 May ;3 a 2.2 3 0.6 b 1.7 + 0.6 mean 2.010.6 June 13 a 2.6 + 0.6 b 2.3 ! 0.6 mean 2.410.6 7uly 13 a 1.9 + 0.6 b 1.5 ! 0.6 mean 1.7i0.6 t

I i

39

i I

i 8 [J\

TABLE 10 (Continued)

I i '

I Environmental Radiological Monitoring Program, Fermi-2 l Preoperational, 1979 i

i Drinking Water - Analytical Results - Gross Beta I

i

{ Compositing Month Sampling Location pCi/112c Aug st 13 a 1.6 1 0.6 b 1.3 + 0.3 mean 1.630.6 i

September 13 a 1.0 3 0.5 b 1.4 + 0.5 mean 1.210.5 October 13 a LT 3 2) b LT 4 i mean i LT 4 O N ovember 13 a LT 2.0 b 2.2 1.1 (3) mean (1/2)

December 13 a LT 4 b LT 2 mean LT 3 (1) Simple average (rou. d) 3 simple avarage (rounded)

(2) LT = Less Than -

(3) Number in parentheses indicates number of detectables/ number of analyses f

o .

40

t r

i F. Milk The analytical results of gamma emitting nuclides in milk are reported in Table 11.

The only nuclides identified during the reporting period were naturally occurring K-40 and Pb-212.

The results of the I-131 analyses performed by radiochemical separaticri are shown in Table 12. The activity on a!! samples was less than the limit of detection. -

l A statistical summary of the analytical data is provided in Table 13.

u 4

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41 NUS CO APO A ATION

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TABLE 12 Environmental Radiological Monitoring Program, Fermi-2

~

Preoperational, 1979 Milk l

Analytical Results - lodine-131 i

Samoling Location pCi/l Co!!ection Date I

Station 7 LT 0.1 i

4-22-79 Station 7 LT 0.3 l 5-13 79 (1) LT = less than 1

S I

1 l

f

'I 43 i

- m. - - . .. . .

-<O.

T Atil 1: 1J O o \

lNR$lt)HH,jjf t : ATtiIN S TAl'is ris 11 9.V Al U A tit lN (NVIMt NMQ!} Al. ItA11(Of fM alt:Al MfitalitilliNi; lluiGft AM sl MI- ANHt) Al Htt'(skT i d 1CE LT NO , 5 ft- 3 41 NAMC Of I AClllOf: I NHit 'O l'Ile MI flNii 2 ItsCATH )N t it' i Ne t i l lY ; 10 Mil l3 E DIlrilWI ST t II' l>I Theil[, PIlt'llit : Ate (1881 Nt,lijnWN ]t_vv[tyt[Q

.. . de l [te . I I H it sil; . it 'l Mitt le laf, { '! 1 tj , {lliu stfGil lAHilAHf S,8?'JU Control Nue l.or el Types es.J Tetet Numil.os I owes limit All I. lli .itte joignWitM!nt ygl Mean Ninw iutines Medluan ur Pethway N u..e Mi an(l) locations S mpled of Analysus ruslia r ed of ggy f ue etauus ,,

14 J e d ?_

Meart(f) g Regnated l >= t ut t ion Me.e.s (I) l11 s t .enre ko'?Ju Mea sin enevnt s (UJit of Mwasuresnent) _ BPd"

_ Il lt. 81 0.17 (a/s) 0.17 (u/Is) 0 0,1514te/46) Statsun 5 Tl 0 - IHres e 11 edletion Gen.ma lloso 54 (0, a l -0. lts) 0.6 ud. NW (0.15-0.lu) (U. 85-0.19)

(mH/ day)

O l' Isle (Pete.s (14vesca:eis) 8 *nu (t) ludicat<*

Canimie Spe c 6 (pCl/kg,wut weiglit) lix.ottosi sanipled J.se in.; s e p..tli.9 gwslial.

3 400C (4/4) 3300 (2/2) 0 (3. wo- 4 J00) (3300- J Jou)

't - 40 0

, g g g, M ii - 5 4 130 (l l.i t 0

<llo 11 0 l'w - 59 260 (Illt < LLI)

Co-58 IJG

' 181) 130 (1881 Go - e.o ' llo O

<llis Zn - 1.5 2 tio 0 r lits

<lll>

(:s -134 lid -

0 59 (2/2)

Cs -137 128 29 (3/4)

(2a-4o), (58 ' bo) 0 58 (1/4) < Itp 1*ls -284 (Su - Sul 0

du (1/4) 24 (2/l) it -211 (J4 50) (24-25) 25 (1/2) n lit - 214 Ilse

( 25 - 2',)

U II! o

1818 (Jts- Jul

'll - 2116 u

tra - 22s 210 (l/4)

(fin - 27 0) e s emp ., ,e

^ f-f;.pl L l a le a N ' t.)

LPfEAftlifj[_AJii 8N S rArtsfit'Al IVAl tlAllON uvinnNurNTALpA_ppitw;IcAl poNlroultu; FHt CHAM SI MI- ANNUM RLTORT Naut Or rAcIllry: temlro rinutt_styt.;

locu:ON Or FACf,ltY: tiOCk L r NO. 50-lit Jo Mills foutilwisy or Dt tuolydtpfl1HiANj RINClifowid TOWN $ltuL lirRHfLNCdpjGIt til('LMif f it 19J18(yelRt elicli {tgtgijl uu Medium er Pethway Type and TAal Numiteur Sempted Iower Ilmle All ladte stor ol hialyses Postoremim! .>I g I.,t ae loeis loc.itives W1Mflggh Contsol Nuot,eg of (Unl of Measurement) Detc. tion ts.. ea . Mean(1) W attons Me..n (1) t it s t..t.g R, w Norumstene

__ (I I l'8 kany Mean (r) 8 Muported R4 e=j e.

Jaca s ..es ..,e ,

bleuswilow St*limaants (pCl/h J,eley weiglet) U.smem.s Spet . 32 l Ss:e n.Av s U lutusMers

$20 (12/12) Sr.sti.we 1 320 (t/4)

(2b0-10003 0 U. 2 an.I . E (78u-4000)

Th Douglitus Ji (12/82) ~ d't."e 9 610 (2/4) 0 t ilio-6 70) 0.2mt. L (570-670)

K - to 14000 (12/82) st.etson s 17000 (2/4) 0 (18000-18000) 0.2 n.l. t (15000-18000)

Cs-IJ4 150 ellD M

Cs -137 150 6bo (4/12) StJet..u V % U(2/48 0 (250-1000) U. 2 ml l' (150- B loul i

Walet. Senfacn a..I Insaking G***d SP*C II (5 OI/IIIcej Tu date.semplies h e a not en in-illeted et tIee Mn-$4 caentful drinkleng 15 (II D "d'.

U O" - O l ., - 5 9 30

< LI I,) ,

O Ci: - 58 15 aflis O

C 2 - 4.4 15 <lll>

0 Zee - e.5 Jin <llie U

Ze - file - 9S to (tils O

g.u 1.10 te/4ti) t,s..e f ore iJ 140 (4/24) IJO (4/s) t u n it,p) 1. 2 n t . s (llo- It.o) u

($ J - Iso)

s TJ.llt i I J It .t # N 'T . t INDICATOtt IOCAflON STATISTD[_t Vgl]AIKM

[fiYll40NMLN,TAl. RAl IOI OCICAL MONITOlllN"*. [R( CH At t SIMI- ANNHAl. p[l'tg NAME t.I' FACIllTY; l't4Miro I'litMj ljulT 2 . I m M 1.LT NO. 5091 IDCATION Ol' FAClllTY: 1st Mll r3 S(stlTI%ji eipt.rligli,Jjle NICAM JHl.Ht'llTOWN TOWtfjjfj[Pj_

B I POftI[NI,' fpl[gl,5; fil t:l tittt H 19, lagtttJ illC Hte ;ll J A[JirAkt *>, }'ffl0 Mudtvsos Pethway Type and Total Numiins lower Linilt All in.It cat ** bylon With tiljhejijlog Control Niember 1,8 Samplod of Assalyses Peslo.sne.1 of gyg lucetionq N emir kican(ll locations Nonroutine (Unit of Mwasurvenwnt) Det us tion klease ill 4 )e sianc e R ame_ Mean (1) R e6=* teil (I l li __ It amo Pose- kteas.ec,.gnes Watur.Siwlace armi Drinking (Con't) C'*IN 35 #IIU (pCI/ Iller) Cs - 137 15 < lits O tsa - Ie - 140 15 ( 81 p

O sta - 226 300 (3/4u) Station i 3 100 (3/48) la o u (90-130) 1.2 me. S (90- 13 u)

Te st lune 24 330

240 (4/6) Statio.e 13 28.0 (t/8) 410(3/8) 0 (190-350) 1. 2 ml. S (190-350) (330-520) letteeking Water Gsons lict.s 24 2 2.5 (19/24) O.ec 0) linlicatos To d.ste, sempatreg has O g;,jl,g, (l.2-3.6) lo. atlun san ploa ..ot 1.cen t..it t ..d at eth ilut t a.3 s o pos t lw; a usita ul Itnotto.s.

G ps-a im?

btot>.m 1 46 (et/g2) 35 (74/74) 0 Alabossou Particulates Gross liete 296 10 40 (218/222)

(ll.-03 pCl/ an3 ) (1-485) 0.6 ml. NNW (3-Il0) (8-90) e Atel.se r..eti. =1..*. . Camnia Spoo 32 (IL or p . .il ,

t * - 13 4 u.ul clipt Stdtio's 4 2.2 (2/8) 0.19 (l/s) o g * . 1, y ""I 0.17 (#/24) I2* I-2 4) (0,19.U . 3 9)

(0, pg.0.2 4) 0.b n.l . N NW Lt't 86" 4 9.0 (5/0) 6 5 (1/81 It., - i s.S (24/241 (2.6-9 II o (4.2-12) 0.6 n.l . N NW (5.b-It) c ,_lgg blotion 5 0.519(2/8) 0.58 (2/u) ,11.9 ,

(0. 4 t,- 0. 70) U.h n.l . taw (o, q s. u. 70)

It,-212 silE8 0.22 (t/8) 0 (0.22-0.2/)

s v . g.

T AMi r. II i 4 :s ill*T )

[NiblC8D34 It H : A,llO!I 'iff t tbilt .Al (VgtlATII DN L

yp(INP1LNTp{. RAplOf f 4;tCAI MONITOHING j'RtIC.UAf t SLMI- ANNil Al RiftJRT NAME Or I ACH ITY: I NH NelilllM111!!!Lj IOGLT NO. 50-341 LOCATION Or FA'JitITY: 30 Mil l'S SOf f TilWI ST til' Inf7HE H T, MICH H :7 t4 (I NI Nrilpy,N TOWhjMRJ, HJWRJ[NG llills)ll; 11100 Mitt H 2's fJ78,_ljlitt >('s;H { ant l AlW 5,1950 Medluen or Pathway Type and Total Nun.hes Lower I tenst All In.Ilsator M.stion With fligheRhicon Control N..mber of Sampled of Anaiyses restisene 1 of utan(0 (2)

(Unit of Measursement) tie testion la.t etung N .p.e g,,,,,'

"'(2) Noru uut t ne M r..n (O Dbt..n. e R ,,eil e Mean (O Itepieted J ll)t) _ 18 ntje 9,ange Meeg..ren nts Milk Gee n Spec e3 T. date. Indic.t.. l. .tluns nest lanellevd. 0 (pell/ liter) t:s - 134 a5 clIJ) 0 Gs - 137 15 (Ill' o a

B.s - l a - 14 0 15 5 81 t3 0 it - 4u 1300 (13/13) 0 (s.'00-1500)

A l>b - 214 24 (1/13) 0

%J (24-24) l - 135 0.5 <III, g

I .

9 (1) lj.D = tower IJmit of Detection as definesd in the USNHO branch *ecta. ital rostalon un re@elogicas environemental enenstorlag.Tatste 3.(Noven.tw 1973.newl.a.,n I).

(?) Mean and range leased upon detectable sneasureements only. Traction of detectalelo spessuren.ents at specilled locetl(,ris is indicete:d in isores.tleeses (1).

(31 take Erle curves t patterne in the l'orn.e-2 arue fluctuate in oppostte direitthens along stuarolino contours fue esspeomen.attly equ.nl durations during en me nuel period. As e result, no "cos tral" locr.tlon is established.

g V. REFERENCES

1. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environ-mental Monitoring Program", Radiological Assessment Branch Technical Position, March 1973.

2. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological En-vironmental Monitoring Progra m," Radiological Assessment Branch Technical Position, November 1979, Revision 1.

3. U.S. Nuc! ear Regulatory Commission, " Instrumentation for Light-Water-Cooled Nu:lcar Power Plants to Assess Plant and Environs Conditions During and Following An Accident," Office of Standards Development, Proposed Revision 2 to Rege' story Guide 1.97, December 1979.

4. National Council on Radiation Protection and Measurements, " Environ-mental Radiation Measurements", NCRP Report No. 50, Washington, D.C.,

December 27, 1976.

3. Oakley, D.C., " Natural Radiation Exposure in the United States", OR P/SID 72-1 Office of Radiation Programs, U.S. Environmental Protection Agency, Washington, D.C., June 1972. ,

P

/

^%

_,)

l

! 48' NUS CCAPORATION

l o

I

- V APPENDIX A t

Deviat:ons in the Sampling and Analvtical Regime t

The following deviations in the Fermi-2 monitoring program have been documented l

I by NUS Corporation and transmitted to The Detroit Edison Company during 1979.

A. Direct Radiation The duplicate TLDs deployed at Station 2 for 1979-Q3 were missing at the time of I collection, September 29, 1979. It is assumed that vandalism was responsible for the loss. The TLDs for 1979-Q4 were placed at this location as scheduled.

B. Fish No sample of yellow perch (Perca flavescens) at Station 11 (C,ontrol) was collected

,_ by biologists from The Detroit Edison Company. Repeated attempts at sampling by (v' the staff were unsuccessful. T'wo causes contributed to the lack of sample: (1) i vandalism of the gill nets (2) the low density of perch due to a walleye "rur" 9

occurring during this period. Responsible staff of The Detroit Edison Company will be evaluating techniques and alternate locations in preparation for subseqct-at collection efforts.

Biologists from Edison collected yellow perch from Station 11 (Celeron Island) in October. Due to the small volume of sample, samples of walleye collected at the same time were also sent to the Radiological Laboratory for analysis. During sample preparation, the technician accidently mixed both species of fish together.

The gamma isotopic analysis was performed on the combined sample.

C. Airborne Particulates During 1979, datn recovery from the air sampling network ranged from 79%

(Station 4) to 65% (Station 1). In Nov mber and December of 1978 (the instrument n

i y 49 i

. NUS COAPOAATION ,

m

l l trial pcriod) and the first half of 1979, data recovery was excellent. The majority of dowr, time occurred in the second half of 1979. Edison owns five air samplers, four deployed at " active" monitoring locations and one spare cait. From June through Octcber, all five units experienced pump freezing which resulted from a breakdown of the 'ubricating oil. The site technician attempted field repairs but fue to the nature of the problem, the instruments were ultimately shipped to the vendor in California for repairs. As repairs were completed, each unit was shipped first to NUS for calibration, and then to the site technician for field deployment.

As can be expected, each shipment of an instrument entailed approximately one week for delivery, plus the requisite time for repairs. As repaired instruments were received and calibrated, they were cycled to field status on an "as available" basis. Based upcn vendor recommendations, a new type of oil is now being used to help eliminate future problems of this nature.

Other difficultes encountered during the year included thermal overloads from cooling fan malfunctions, broken ventur! tubes creating logs of vacuum, and, most recently, vane deterioration.

I I g

Edison is evaluating a program to improve field data recovery based on the identified common failure modes of the instruments. The program includes:

e purchase of one additional instrument e purchase of two (2) each of complete subassemblies of those components which experience has shown are particularly subject to failure e stocking an increased inventory of miscellaneous spare parts and increased frequency of preventive maintenance (such as periodic replacement of pump vanes etc.).

The intent of these steps is to allow immediate field replacement of malfunctioning units, and field repair of them with complete subassemblies if necessary. Increased frequency of replacement of wearing parts should also avoid some field failures. ,

i > .

50 .

6 NUS CORPORATION

D. Water 9

An insufficient sample for gamma analysis was collected at Station 14 (Trenton Channel) for the first half of 1979. Numerous attempts at repairs proved unsuccessful, although immediately following repairs, and for up to one week af ter repairs, the instrument h'ad been observed to be perforn ing satisfactorily. Ice formation, clogged sampling lines, and the ten foot vertical pull to the sampling head contributed to the lack of sample. A larger pump head and sampling line were installed in August with acceptable results. Installation of a new sample head anc' increased diameter tubing was delayed from the expected installation date by vendor back order.

No water sample was collected from Station 14 (Trenton Channel) for the month of October. During the scheduled sample co!!ection, the site technician discovered ,

that the interval sampler had been turned off. It is assumed that an Edison employee inadvertently shut the sample off since that instrument is located in an area where access to the property is controlled by Edison. ,

O ,

V E. Milk As a result of a personnel error in the execution of a computer command, the acquired gamma spectrum for the April milk sample from Station 7 was lost. The sample was recounted at a later date; but because of the delay, the detection limit for Ba-La-140 could not be achieved.

1 1

l l

1 l

[ ,0 -

t i l

y l 51 1

NUS COAPORATION b

I l

lI APPENDIX B

.Laboratorv Ouality Assurance

1. Introduction The quality assurance program of the Radiological Laboratory of NUS is briefly described in this appendix.

Information on each incoming sample is entered in a permanent tog book. A sample number is assigned to each sample at the time of receipt. This sample number uniquely identifies each sample.

Separate .'aboratory notebooks are used for each major environmental monitoring program.

s j g Laboratory counting instruments are calibrated, using radionuclide standards ob-tained from the , National Bureau of Standards, the EPA, and r eliable comrrercial suppliers, such as Amersnam-Searle. Calibration of counting instruments is main-tained by regular counting of radioactive reference sources. Background counting rates are measured regularly on all counting instruments. Additional performance checks for the gamma-ray scintillation spectrometer include regular checks and adjustment, when necessary, of energy calibration.

Blank samples are processed, with each group of samples analyzed for specific l radionuclides, using radiochemical separation procedures. Blank, spiked (known

quantities of radioactivity added), and replicate samples are processed periodically

( to determine analytical precision and accuracy.

l

11. Laboratory Analyses for Quality Assurance The quality assurance procedures employed in the conduct of radiological mon-l ltoring programs by the Northern Environmental Services Division Radiological l

52 l

I NUS CC APORATION

Laboratory are as required in Section 5.0 of the Environmental Systems Group Quality Assurance Manual e.nd detailed in the NUS Radiological Laboratory Manual.

I I These procedures include the requirement for (1) laboratory analysis of samples distributed by appropriate government or other standards-maintaining agencies in a laboratory intercomparison program, (2) analysis of some of the client's en-vironmental samples split with other independent laboratories, and (M analysis in duplicate of a specified fraction of the client's environmental samples.

A. Samples Split with Independent Laboratories Aliquots of shoreli: sediments collected in October from Stations 9 and 10 were sent to an independent laboratory for gamma analyses. The results are listed in Table B-1. Considering the low levels of radionuclides present in the : :mples and the difficulty included in processing sediment so that replicate, homogeneous portions may be obtained, the agreement between the results is considered good. -

Samples of water collected in December from Stations 12 and 14 were sent to an independent laboratory for gamma analysis. Composites of water for Q 4 collected from the same locations were also split for tritium analysis. The results of these analyses are shown in Table B-2.

Af ter analysis at NUS, the December milk sample from Station 7 was sent to an independent laboratory for gamma isotopic analysis. The results appear in Table B-3.

B. United States Environmental Protection Agency Intercomparison Program ,

'!he NUS Radiological Laboratory participates in the U. S. Envircomental Radio-activity Laboratory Intercomparison Studies (Cross-check) hogram. The NUS results of analyses performed on samples pertinent to the Fermi-2 program during 1979, and the known values are listed in Tables B-4 through B-7.

Q'v 33 r

NUS CORPOAATION

^C . .

C. Thermoluminescent Dosimeter Intercomparison q

The Laboratory also part.'cipated in the Fourth International Intercomparison of Environmental Dosimeters in 1979, the NUS results, calculated exposures, and means cf all participants are listed in Table B-9.

D. In-House Duplicate Analyses The majority of analytical work for the Fermi-2 program during 1779 was performed in duplicate / replicate and has been add essed in Tables 3 through 12.

s 4

1 t

l 1

s

.g

! NUS COAPOAATION

T

~ * ::~-- _ -

TAnLE n-1 t

Envirorunental Radiological Monitoring Program, l'ermi-2 PreoperaticMI,1919 Shorell,e 5ediments - Insteperwtent Laboratory Results Gamma Dnit ting Nuchdes, pCi/kggg, I2a Collection Sampling K 40 C s-I h Cs-I 37 Co-60 Otleers Date Loca tion (I Daup;:.ters Th Daugfiers Quar ter I' 15000 I 2000 LT 40 21 1000 I 100 190 I 50 ND( "

t 10-3 79 9 NR 1800 I 600 L T 20 LT 20 LT20 NI)

NR 230 2 20 11000 I 1000 10-3-79 10 va tn

/

(!) NR = Not Reported *

(2) LT = Less Than (3) ND = Not Detected O

e

. ~O o , .

TAnLE n-2

' Environenental Radiological Monitoring INograin licoperational, 1979 1

$awlace Water linicpermkeit Latx>ratory flesults l Gainrna Ernitting Niecliiks

. pct /l I2.. pci/l 12.

Collec tion Sampling Quar ter Ib te Loca t eori CS Ill Ottices II.)II' ,

f LT38 ' ND 0 I 100 4 12 29-79 12 1 .

i 12 29 79 it LT IS ND 0 f 100 l

t (n

j m (1) Quarterly cornposite

(2) LT = Less Tfian (3) ND = Not Iktected 1

,I ..

i 4

l l

i 4

I l

O

. m-9 g e

!/ IDLE 113 i Environ.nental '4mtiological Monitoring Program Preope s tion.il, 1979 i

Milk Indeperwient Laimratory Results Collection Sarnplirig Jamena rmitring Nuclide2.pCaf ! 7, I

Quar ter T) ate Loca tion t's- 131 K 40 Ottier s Nn I2I II 4 12-29 79 7 LT% 2fs00 I 1300 I

i I,

(1) LT = Less Than (2) ND = Not Detected Va N

,ei i

I a

e I __

l TABLE B 4 United States Enuronmental firotection Agency Intercomparison Program - 1979 Analytical Results - Gros. Beta in 4'ater Month Known Value NUS Value pCi/l ! 30 pCi/l ( '

i i

January 16 1 15 15 March 16 ! 15 16 May 22 1 15 ,

22 September 40 . 15 9(2)

November Sample d stroyed in shipment to NUS (1) Mean of three reported values l

(2) Investigatien of NUS reported result revealed that a probable technician error was responsible for the NUS value being low by a f actor of five. Technician used 200 mls of sample for the analysis but calculated the results based on one liter, the volume normally used.

i l

l l

l f

i 'N

! ,58 NUS CORPORATION I

m

TABLE h-3 United States Envkonmental twotec:M Agency Inte. comparison Program - 1979 Analytical Results - Gamma in Milk ,

NUS Value I' fpCill)

Known Value (pCi/I ! 3o )

(Li.140 K (mg/l)

Cs.137 Ba.140 K(mg/l I3) 1 131 Cs.137 Momfi My LT ll II 1350 1560 ! 234 94 48 Lanuary 103 I 13 49 I IS 0 m GE(Li) at vendor for repairs - no data reported LD 96 f 15 154 2 24 0 l>60 I 234 April

67) 30 LT 19 1634 49 2 13 0 1470 2 219 N >vember 637 ! 96 (t) Mean of reported values (2) LT = Less Than

Ih TABLE B-6 -

1 I United States Environmental Protection Agency Intercomparison Program - 1979 Analytical Results - Tritium Month Known Value NUS Value (pCi/l ! 30 ) Ci/l) (I' February 1280 I 993 1400 April 2270 I 1047 g 1930 s

O aune 15 0 : 1010 1 10 October 1560 1 1111 1370 (1) Mean of reported values l

l O

60 NUS COAPOAATION

I I

If N e 2, = o.

g ,A 1 b. > >

G .e .a a

o e 4

E >

s a

m

.~

=e .o O 1 o o-e 5.g & so g $I b. k k.

zl a a a g

r O et O e Z ai N -

j e c e.

. D. D.

A NI .J .J .

F.

e C

C P

- o -

.b b

.J h b

.1 o w

.J.=

~

=

% O 4

2. .$. _

e

~

N N

C 9 e E > > >

~

.u. .c.

l4 a a "

E 2 ,

> c e c

~ - -

~. x. =, e i g g e - .. o ..

W < '

G N

- C a k

=

e e J

b & s e - e "g C e'

~

$ 4. *8

- .Y

==

Y 4 ~ h 1

5 .D =

G g

3 3 4 #= 4 5 *. 2 2 C . O O o

R 4 Z

.c .-

C 2

- .=

C g e l 3 > - P, e e., .. e o ;

7_ - . - y Z N N g

-g x

C e -IW W - e O - - g W ee

e *e 6 $

V e e * , g 2

.= ne 8's &

=

D 89

- ..

e 5 e g 3 W L

O O EA e L -

t .

1

m. e 0 .a 9G=

- k*A e n O I E d Z l k 5-I 2e

$ y -N e 2 L s - - -

l 61

- - ~ ~ - - - - - - _ ._ _ . , .. . , -

./- .

TABLE B-8 United States Environ.nental Protection Agency Intercomparison IYograin - 1979 Analytical Results - Cs-137 and Gross Deta - Air Filters ,

Known Value (pCi I 3o) NUS Valt-jgCi) I' Cs-137 Gross Beta Cs-137 Gross Beta Month 18 I 15 9 22 January 6 I 15 63 I IS NR 76

$ March 21 I 15 31 I 15 17 37 October 12 I 15

~

j (1) Mean el reported values

.(2) Nk = Not Reported (GE(Ll) at vendor for repairs) e

i i

TABLE B-9

[I; j Fourth International Intercomparison of Environrnental Dosimeters - 1979 i

1 j Analytical Results - Mean mR I 2c 1

l NUS Value Calculated Exposure All Dosimeters 3

3 Laboratory " Low" 9.9 I 1.4 12.2 1 2.4 12.0 I 7.6 l

i i 43.9 I is.2 -

Laboratory "High" 37.8 I 3.5 45.8 I 9.2 I

13.2 1 1.5 14.1 ! 1.4 16.0 I 9.0 Field e -

(1) Value determined from a continuously operated recording pressurized ion chamber, i

o l

l 1

l l

l i O O

1 s 1

63

NUS CORPOAATION

I O

APPENDIX C Analytical Procedures Environmental samples for the Fermi-2 environmental radiological monitoring program were collected and analyzed in accorcance with procedures described in detali in the NUS Laboratory Manual " Environmental Monitoring and R'adiological Services Procedures / Work Instructions." These analytical procedures have been adapted from the published analytical methods of the Environmental Measurements Laboratory (EML - formerly HASL), the laboratories of the Environmental Protection Agency, and pertinent ASTM procedures.

a O

e

(_)

64 .

NUS CORPORATION

I k APPENDIX D ,

Peporting of Analytical Results

~

In the tables presenting analytical measurements, the calculated value is reported with the two sigma counting error (2a) derived from a statistical analysis of both the sample and background count rates. The precision of the results is influenced by the size of the sample, the background count rate, and the method used to round off the value obtained to reflect the degree of significane of the results. For analytical results obtained from gamma spectral analysis, the precision is also influenced by the composition and concentrations of the radionuclides in the sample, the size of the sample, and the assumptions used in selecting the radio-nuclides to be quantitatively determined. The two sigma error for the net counting rate is:

'

b N

g 2 +

< t I s b where 4

R 3

= sample counting rate Rb = background counting rate l t 3

= sam,nle counting time t

b

= background counting time If the measurements on the samples are not statistically significant (i.e., the two sigma counting error is equal to or greater than the net measured value), then the radioactivity concentrations in the sample are considered nor-detected.

9 .

65 i

NUS CCAPCAATION

i O aesuits ,enorted es iess then "tr - ere beiow the iomer iimit of eetection (ttD).

, The LLD is defined as the smallest concentration of radioactive material in a L

sample that will yield a net count (above system background) that will be detected t

with 95% probability with only 5% prcbability of falsely concluding that a blank observation represerits a "real" signal.

For a particub? measurement system (which rnay include radiochemical separation):

l

[ LLD = 4.66 s b

E x V x 2.22 x Y x exp (- A At)

I l where I

f I LLD is the lower limit of detection as defined above (as pCi l

. per unit mass or volume) 4

' i

, lO s b

is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as f

counts per minute)

E is the counting efficiency (as counts per disintegration) j V is the sample size (in units of mass or volume) l

' 2.22 is the number of disintegrations per minute per picocurie q Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the pa-ticula radio-nuclide I

l 6t is the elapsed time between sample collection and counting O

J 66 NLS CORPORATION l

?

u ,

i li ( The follewing are definitions or descriptior.s of statistical terms used in the j reporti".g and analysis of environmental monitoring results.

Precision relates to the reproducibility of measurements wi*hin a set, that is, to

, the scatter or dispersion of a set about its central value.

1 l '

Measures of the Central Value of a Set. Mean (or Average or Arithmetic Mean) is L the sum "e X. of the values of individual results divided by the number of results in the set. Yhe mean is given by i

e n

X =

(Xg+X2+...X'I""E X;/n n

! . i=1 Measeres of Precision with a Set. Standard Deviation is the square root of the quanti y (sum of squares of deviations of individual res,ults from the mean, divided by one less than the number of results in the set). The standard deviation, s, is V given by:

s= (X g - X)2 / (n - 1) i=1 Standard deviation has the same units as the measurement. It becomes a more reliable expression of precision as n becomes larger. When the measurements are independent and normally distributed, the most useful statistics are the mean for the central value and the standard deviation for the dispersion.

Relative Standard Deviation is the standard deviation expressed as a fraction of the mean, s/ I(. It is sometimes multiplied by 100 and expressed as a percentage.

Range is the difference in magnitude between the largest and smallest results in a set. Instead of a single value, the actual limits are sometimes expressed (minimum

, value - maximum value).

9 -

67 NUS CO 1PORATION

- - - _______-____________-______

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